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Chernobyl Nuclear Accident Congressional Hearings Transcript

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225<br />

Jan Beyea and Frank von Hippel<br />

Containment of a reactor meltdown<br />

Any good scientist or engineer believes<br />

implicitly in Murphy's law: "If<br />

something can go wrong, sooner or<br />

later it will go wrong." The U.S.<br />

Atomic Energy Commission, which<br />

until 1975 had the responsibility for<br />

ensuring the safety of U.S. civilian<br />

power reactors, had many good scientists<br />

and engineers involved in its<br />

work. And during its history it repeatedly<br />

considered the consequences<br />

of all<br />

the safety systems in a nuclear<br />

reactor failing, the fuel melting and<br />

the volatile radioactive isotopes in the<br />

fuel being released to the atmosphere.<br />

The answer which came back from<br />

major studies in 1957 [1], 1965 [2] and<br />

1975 [3] was always that the consequences<br />

could be very serious indeed.<br />

This finding underlined the importance<br />

of preventing nuclear reactor<br />

meltdown accidents. As a result, the<br />

Atomic Energy Commission and the<br />

<strong>Nuclear</strong> Regulatory Commission<br />

(NRC), its successor in the area of<br />

nuclear safety regulation since 1975,<br />

required so many redundant safety<br />

systems on nuclear power plants that<br />

both nuclear regulators and the<br />

nuclear industry became convinced<br />

that the likelihood of a reactor<br />

meltdown accident had been reduced<br />

to a negligible level.<br />

The massive failure of safety systems<br />

and the associated confusion<br />

which has occurred repeatedly at nu-<br />

Figure 1<br />

LARGE VOLUME PRESSURIZED WATER CONTAINMENT<br />

Figure 2<br />

SMALL VOLUME BOILING WATER CONTAINMENT<br />

CONTAINMENT<br />

HEAT REMOVAL<br />

IfiE COOLANT<br />

SAFETY INJECTION<br />

Because of its large volume {about 60,000 cubic meters), this containment<br />

can hold all of the steam released in the first minutes of a<br />

loss of coolant accident. Subsequently steam pressure should be reduced<br />

by the containment water sprays.<br />

The combined volume of the drj' well and the connected free space<br />

over the pressure suppression pool is only one eiglh that of the containment<br />

shown in Figure I. Steam from the dry well bubbles through<br />

the water in the pressure suppression chamber and is condensed. This<br />

could prevent overpressurization by steam but not by other noncondensable<br />

gases such as hydrogen and carbon dioxide.<br />

Source: T.J. Thompson and J.G. Beckerly. The Technology of <strong>Nuclear</strong> Reactor Safety, vol. 2, chap. 21 (Cambridge, Mass.: MIT Press, 1973).<br />

52

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